ML20147J154
| ML20147J154 | |
| Person / Time | |
|---|---|
| Site: | 07000709 |
| Issue date: | 09/29/1978 |
| From: | Carolyn Cooper, Fou C, Trabant E DELAWARE, UNIV. OF, NEWARK, DE |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 7810270262 | |
| Download: ML20147J154 (60) | |
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RECEP$Eptember 29, 1978 5
Division of Fuel Cycle & Material Safety
$13 GCT 4 p*u 11 04 Radioisotope Licensing Branch Office of Nuclear Material Safety 6 Safeguards U.S. Nuclear Regulatory Commission qG, C_,
Washington, D.C.
20555
,,a Re:
SNM-656 Docket No:
70-709 RIS:
ZEZ Gentlemer:
The Uhiversity of Delaware, Newark, Delaware hereby makes application for renewal of Special Nuclear Material License Number SEM-656.
I The following information is submitted in seven(7) cot ies in fulfillment of Section 70:22, Title 10, Code of Federal Regulations, Part 70 "Special Nuclear Material" and in accordance with U.S. Nucicar Regulatory Commission Regulatory Guide 10.3, Sections 4 and 6.
1.'
Specification of Applicant The University of Delaware, Newark, Delaware was made a Land-Grant College by act of the Delaware General Assembly in 1857.
It is thus organized in and by the State of Delaware.
The principal office of the University is located in Hu111 hen Hall, University of Delaware, Newark, Delaware 19711.
The principal officers of the University are:
Name Title Address Citizenship Edward A. Trabant President 47 Kent Way United States Newark, DE 19711 L. Leon Campbell Provost & Vice 76 Polly Drummond Rd.
United States President for Newark, DE 19711 Academic Affairs There is no foreign control or ewnership exercised over the applicant by any alien, foreign corporation, or foreign government.
2.
Specification of Activities One Pu-Be neutron source M233 will continue to be held in storage a.
by the Department of Electrical Engineering in Room 241 of P.S.
duPont Hall Laboratory, Main Campus, o r used As sa calibration source for neutron detection instruments. ]LG a 2 g t o.1 1 O
b.
One Pu-Be neutron source N800118 will continue to be used in the Nuclear Physics Laboratory of Sharp Laboratory, Main Campus.
The source will be used for educational instructional purposes.
It will be used in the two specific experiments in the second half of the one year senior laboratory course PS 617/618.
- 1) n-gamma discrimination A liquid scintillator NE-213 will be placed near the howitzer's side port to detect the neutrons and gamma photons.
Standard pulse chape discrimination technique will be applied for distinguishing neutrons from gamma counts. The student will be sitting in the control room of the accelerator laboratory with the electronic console. The signals from the liquid scintillator are sent through a conduit under ground via coaxial cables.
4
- 2) neutron activation analysis A short-lived isotope like Mn-56 will be produced by irradiating Manganese powder in plastic pouches. The pouches will be placed in the lucite sample-holding rod of the howitzer. The rod is then slid into the vicinity of the source inside the howitzer for irradiation. After irradiation'the rod can be pulled out and i
the activity will be counted in standard gamma photon counting set-up in the nearby laboratory reserved for the PS 617/618 course.
In both experiments the Pu-Be source shall remain inside the howitzer and the howitzer will be kept inside the accelerator vault.
3.
Specification of Special Nuclear Material The University of Delaware possesses two(2) Plutonium-Beryllium sources totaling approximately 96 grams of Plutonium in source Nos., M233 and N800Il8 given in Grant Number MG-179-73 RIS:ZEZ to the University of Delaware by the Laboratory Relations Branch, Division of Nuclear Education and Training, USAEC, on February 13, 1973. This grant replaced Loan Agreement R2(1958) and 62-6.
a.
Source No. M233 of anproximately 16 grams of Plutonium and one(l)
Curie of activity was manuf actured by Monsanto Research Corporation, Mound Laboratory, Miamisburg, Ohio.
The source is stored and secured by lock and key in its original shipping container which is a 15-gallon drum filled with paraf fin.
The shipping container has a 15-inch diameter.
The source is described as 15.93 grams Plutonium contained in Tantalum and stainless steel having dimensions of 1.06" 0.D. x 1.58" H, 10-32 thread, b.
Source No. N800Il8 of approximately 80 grams Plutonium and 5 Curies of activity was fabricated by Nuclear Materials and Equipment Corporation, Apollo, Pennsylvania.
The source is stored, used, and secured when stored by lock and key in a neutron howitzer model NR-2 manufactured by U.S. Nuclear Corporation, P.O. Box 208, Burbank, California. A print of the details and dimensions of this howitzer were enclosed with the University's previous application dated October 10, 1962. This print is U.S. Nuclear drawing number E-0050.
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The source is described as 74.42 grams Plutonium contained in Tantalum and stainless steel having dimensions of 1.63" 0.D. x 2" H.
c.
This renewal application requested a possession limit of ninety-six (96) grams of Plutonium encapsulated as two(2)
Pu-Be neutron sources.
4.
Technical Qualifications of Personnel Course Instructors.
Cheng-Ming Fou, PhD., Associate Professor of Physics 1956 B.Sc. National Taiwan Universi';y, Taiwan China 1961 Dipl. Phys. Universitut Munchen, Munich, Germany 1965 PhD.
University of Pennsylvania, Philadelphia, Pa.
1965-68 Research Associate, Univ. of Penn., Tandem Accelerator Laboratory 1968 Assistant Professor of Physics, University of Delaware 1972 Associate Professor of Physics, University of Delaware Recent Publications Investigation of B and Be Levels in Kinematically Complete B(p,pn) Be, J.M. Chou, C.M. Fou, C.S. Lin, Y.C. Liu, P.S. Sung, and M. Wen, Journal of Physical Society of Japan, 44, 1 (1978).
Characteristics of the First Excited State of He-5, C.M. Fou, Y.C.Liu, C.C. Hsu, and S.L. Huang, J. Phys. C. 11, 847 (1976).
Study of Multi-particle Final State Interaction with a Pulsed Beam, J.C. Chou, C.M. Fou, C.S. Lin, Y.C.Liu, P.S. Sung, and M. Wen, Nucl. Instr. Methods 130, 157 (1975).
The Characteristics of the Third Excited State of Li-6, H. Schwartz and C.M. Fou.
J. of Phys. G7,, L57 (1975).
The Excitation Energy of the First Excited State of Be, C.M. Fou and P.T. Wu, Canadian J. Phys. (1975).
The Characteristics of the First Excited State of Li, R.M. Cagne nad C.M. Fou, Journal de Physique 36, 759 (1975).
Dr. Fou has served on the Radiation Safety Committee of the University of Delaware since 1976 and served as chairperson of that committee during the 1977-1978 academic year. He is also an authorized permit supervisor under the University's Broad "A" NRC license #07-01579-19.
C.B. Cooper, PhD., Professor of Physics 1950 PhD., Physics, University of Maryland 1944-46, Technical Supervisor, Manhattan Project, Oak Ridge, Tenn.
j 1946-49, Instructor, Physics, University of Delaware 1951-52, Assistant Professor of Physics, University of Maryland 1952-58, Vice-President, Tageraft Co rpo ra tion l
1958-65, Associate Professor of Physics, University of Delaware 1965 Professor of Physics, University of Delaware 1968-69 Acting Chairperson, Dept. of Physics, University of Delaware i
Recent Publications Analysis of Pb-azide Thin Films by Rutherford Backscattering, H.M. Windawi, C.B. Cooper, and F.E. Williams, J. Appl. Phys., 47, 3418 (1976).
AES Depth Profiling with N,+ Ion Sputtering, H.M. Windawi, J.R. Ratzer, and C. B. Coope r, Phys. Lett.
(Neth.), 59A, 62 (1976)
A Combined UHV Ion Scattering and Secondary Ion Mass Spectrometer Utilizing a Magnetic Sector Magnet, L.L. Tongson and C.B. Cooper, J. Phys. E., 10, 1245 (1977).
Dr. Cooper has been active in the field of surface physics for about thirteen years.
He has in addition to the above publications about 35 others.
Dr. Cooper serv 8d as Radiation Safety Officer for the University duri:
l963-1965 and has been supervisor of NRC license #SNM-656 for a number of years.
Radiological Safety Jenny M. Johansen, M.S., Safety Coordinator / Radiation Safety Of ficer 1965 B. A. Concordia College, tborhead, Minnesota 1969 M.S. Radiological Health Physics, North Dakota State University, Fargo, N.D.
1969-70 Research Assistant, Radiation Safety Of ficer, Virology and Tissue Culture Lab., Tuf ts Medical School, Brockton V. A. Hospital, Brockton, Mass.
1970-71 Health Physicist / Chemist, Radiation Safety Officer, Division of Nuclear Medicine, Peter Bent Brigham Hospital, Boston, MA.
1970-74 Health Physicist, Assistant Radiation Safety Of ficer, Joint Center for Radiation Therapy, Bostor. MA.
1974 -
Radiation Safety Of ficer, University of Delaware.
1975-Appointed Instructor, College of Graduate Studies, University of Delaware 1976 - Safety coordinator / Radiation Safety Officer, University of Delaware.
Ms. Johansen has extensive experience with handling, storage, and safe use of the various radioactive nuclides used in Nuclear Medicine, Radiation Therapy, and Re s ea rch.
In addition, she is the Radiation Safety Officer of record under the University's NRC Broad"A" license 07-01579-19 and serves as Executive Secretary of the Radiation Safety Committee.
Complete lint of radionuclides Ms Johansen has used listed in the Calversity's application for Broad "A" license dated December 3, 1974.
Ms. Johansen also teaches a course on safe handling of radionuclides to graduate students who are going to use radionuclides in research.
Supervisor Source #FC33 (in storage)
Bruce C. Lutz, Ph.D., Professor of Electrical Engineering 1942 B. A. Physics University of Western Ontario 1944 M.A. Physics 1954 Ph.D. Physics, Johns Hopkins University 1944-45 Instructor, Lieutenant RCNUR 1945-47 Lecturer in Physics, University of Manitoba 1947-55 Instructor in Physics, University of Delaware i
1955-57 Assistant Professor of Physics, University of Delaware
)
1957-62 Associate Professor of Physics, Electrical Engineering, University of Delaware 1962 Professor of Electrical Engineering, University of Delaware j
Dr. Lv;> ins served as supervisor of NRC License R-043 covering the ACN-201 nuclear reactor 1;aa 1958 until May,1978. License R-043 has been terminated by the NRC as the reactc. was defueled and deconmtissioned in December of 1977. Belore the time of the defueling, the Pu-Be neutron source M233 previously covered by R-043 was transferred to NRC License #SNM-656 by Amendment #3 dated October 17, 1977 and requested by letter dated September 23, 1977.
Dr. Lutz has held a Senior Operator's License # SOP-313 and supervised NRC (AEC) license 07-01579-02 before its termination in 1975.
Dr. Lutz has served on the Radiation Safety Committee since it was formed in 1957 and was chairperson during the 1975-76 academic year.
5.
Description of Equipment, Facilities and Instrumentation a.' Remote handling tools Source No. N800118 has a two foot long handlins; tool supplied by U.S. Nuclear Corporation.
Source No. M233 has a two foot long handling tool which is attached to it.
b.
Storage containers, facilities and instrumentation
- 1) Storage containers are previously described under items 3a and 3b, and provide adequate shielding of the neutron sources.
In addition, source No. N800118 in its howitzer is stored inside the van de Craf f accelerator vault which is located in the basement of Sharp Laboratory. The vault is surrounded on all sides by high density concrete 90 cm thick. Signal cables are pulled through underground con-duits and the entrance to the vault. is shielded by a concrete maze. The door to the maze contains 2 cm thick lead.
The door to rooms 0140, D, E, which is the j
accelerator complex is kept locked when an authorized person f rom the Department of Physics is not in the immediate area.
l A diagram of Sharp Lab basement is attached to this application.
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- 2) Source No, M233 is stored in a small room within Room 241, p.S. duPont llall.
This small room formerly contained a j
250 Kev x-ray unit which k s been removed.
In the walls, doors, ceiling and floor of this small room is 1/4" lead shiciding.
The door to Roam 241 is kept locked unless used by an authorized person from the Department of Electrical Engineering. These persons do not enter or use the small x-ray room.
A diagram of p.S. dupont flall is attached to this application.
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Radiation detection instruments The following radiation protection instrumentation is available for Source No. N800118:
i Instrument 6 Manufacturer Radiation Detected
)
Alpha Survey Meter, Nuclear-Chicago Alpha Corporation, Fodel 2672 Neutron Survey Meter, Nuclear-Chicago Fast & thermal neutrons Model 2671 Description of the above instruments:
4 Nuclear-Chicago Corporation Alpha survey Meter, Model 2672 -
This instrument consists of a count rate monitoring unit, and an alpha probe that houses a thin window air proportional detector with a high gain pre-amplifier. The probe has a window with 80 cm2 of sensiti,ve area. Sensitivity to a point source at the center of the window averages 90% of maximum.
The efficiency is approximately 12% for alpha particles from rad + E or Uranium Oxide (for 2x geometry). The efficiency for betas and gammas is 0.1%.
The maximum background is 5 cpm, or about 0.0833 counts /second.
Nuclear-Chicago Model 2671 transistorized neutron portable sur-vey meter. This instrument consists of a Nuclear-Chicago Model 2646 Neutron detector and Model 2673 neutron portable count rate meter. The instrument is intended for general survey work for detection of fast neutrons.
By removal of the wax moderator and cadmium shield from the detector tube, the r
Model 2671 may be used for detection of thermal neutons. Gamma discrimination for the Model 2671 is such that a negligible response is produced in a gamma flux of $ roentgens per hour i
from radium.
The Model 2646 Neutron Detector has a sensitivity for neutrons such that approximately 1 count per second is produced in a flux of 10 neutrons per square centimeter per second from a radium-beryllium neutron source. The sensitivity for thermal neutrons without the wax moderator and cadmium shield is approximately 3 counts per second produced in a flux of 10 neutrons per square centimeter per second. The moderator is approximately one inch of wax.
A 20 mil cadmium shield extends along the length of the tube, but the end is left open.
The detector tube is a BF3 gas filled chamber for proportional counting having a pressure of 30 centimeters of mercury.
The detector is not sensitive to alpha, beta or gamma radiation fields of high intensity.
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In addition the Radiation Safety Of fice has on hand the following instruments available to use for both neutron sources:
Radiation Window Instrument & Manufacturer Detected Sensitivity mg/cm2 Use Victoreen-490 with
'0-80,000 cpm 489-35 probe u,
S, Y 0-20 mR/hr 1.4 Survey 489-4 probe S, y 0-80,000 cpm 30 Survey 0-20 mR/hr 489-50 probe Y
0-200 mR/hr Nal(Tl) lxl" Survey Vic to reen-440 S, y 0-300 mR/hr 3.0 without Survey Measuring cap Victoreen-444 u, S, y 0-300 mR/hr 1.5 Survey Monitoring Victoreen Radector III S, y 0.1 mr/hr-1 Kr/hr Monitoring Eberline PAC-4G-3 Survey with AC21 probe u
0-500,000 cpm 0.85 Measurement i
Survey AC21B probe S
0-500,000 cpm 0.85 Measurement Survey TP-1 probe S
0-500,000 cpm Windowless Measurement Survey Eberline PNR-4 q
0-5,000 MREM Measurement Assaying Eberline MS-2 with u,
8 0-500,000 cpm Windowless Measuring proportional gas flow FC-1 detecto r Calibration of Survey Meters n-Detection instruments will be calibrated at various distances in air against the 1 Ci Pu-Be neutron source #M233 which has a reported flux of 1.86 x 106 n/sec (1962). We will assume an average neutron energy for Pu-Be of 3.4 MeV (NBS publication 456 " Measurement for the Safe Use of Radiation, andaconversionfactorofapproximately28x10g.89,1976)n/cm2 = 1 Rem (General Dynamics Health Physics Handbook, p. 163, 1963). The assumed radiation flux relation to source strength for point 2
& = S/ (4nR ) where 4 is n/cm2/sec, s is n/sec and sources is R is distance in cm.
Relationship of $1
- 42(R /R )2 is used.
2 I The source was given to the University by AEC, traceabic to NBS is assumed.
Concrete shielding is placed on three sides of the Pu-Be source for protection. Detection chambers and survey meter are separated by a 36" cable.
PuBe source has a tolerance distance in air of 22 inches giving 55 n/cm/sec which is equivalent to 0.3 Rem in 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> exposure.
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, Alpha detection instruments and probes are calibrated against 4-Eberline Certified Pu-239 sources traceable to NBS within a 0.2% agreement.
The sources are of 0.0003 uCi SN#7418, 0.0030 uCi SN#7419, 0.0337 uCi SN#7410, and 0.3731 uCi SN#7421, giving disintegration rates of 690 + 15, 6,700 1 130.
74,700 i 1,500, 827,400 1 16,500 assuming 1.5% backscatter of alpha particles from the surface of the disk and 2m geometry in the source holder in which the source is recessed by 1 mm.
The instruments are calibrated on 2 scales compatible to sources with the probe at a distance of 1 mm from the surface of the a source, instruments will be adjusted to read within i 10% of source values.
Beta detection instruments and probes are calibrated against 4-Eberline Certified Tc-99 sources traceable to NBS within a 0.2% agreement. The sources are of 0.0002 uCi SN#7415, 0.0025 uCi SN#7416, 0.0256 uCi SN#7417, and 0.2289 uC1 SN#139/71, giving disintegration rates of 550 i 15, 5,650 i 170, 56,820 1 1710 and 507,500 1 15,200 assuming 25% backscatter of beta particles from surf ace of the disk and 2n geometry in the source holder in which the source is recessed by 1 mm.
4 The instruments are calibrated on 2 scales compatible to the source with the probe at a distance of 1 mm f rom surface of the source, instruments will be adjusted to read within 1 10% of source values.
Camma detecting instruments and probes are calibrated against a j
100 mci CS-137 USN type 375, SN F171 source mounted in a JLS Series 10 Calibrator, SN 598 as is directly traceable to NBS, having an output of 100 mR/hr at 50 cm
'l and a 200 beam part.
The instruments and probes are calibrated at certain distances in air along the center of the beam port which will give a 1/2 scale reading at 2 scale settings on the instrument.
The distance from the source for 1/2 scale reading is first calculated.
With the port of calibrator closed, the instrument is placed in line with the calibration port at the distance calculated and measured. The scale on the instrument is placed so it can be seen from behind the calibrator. The calibration port is then opened and the exposure rate on the instrument is read. The port is closed and adjustments made to the instrument if necessary to bring the reading to +10% of exposure rate calculated for the distance. The process is repeated until the adjustment to 110% is reached.
The person performing the calibration is always behind the calibrator when the beam is open. The port is opened with a remote handling tool.
If the instrumeut cannot be placed so the scale is readable, a mirror is placed so that the scale can be seen from behind the calibrator.
Binoculars are also available so that the scale can be seen with greater accuracy from behind the calibrator.
Calibrations are performed by either one of the course instructors or the Radiation Safety Of ficer at six month intervals at the location of the Pu-Be source in duPont llall or the basement of the Radiation Safety Of fice.
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h 6.
Procedures to protect Health and Minimize Dancer The very first lecture of the PS 617/618 course using Source I
No. N800I18 will be on radiation safety in which the relevant paragraphs of the University of Delaware Radiation Safety tbnual (UDRSM) will be explained, j
The use of radiation monitors and survey meters will be shown.
Throughout the semester at each laboratory session, the area which the students occupy while the experiment is in progress will be surveyed t
to. ascertain the radiation levels.
Each student will carry a personalized pocket dosimeter.
The readings of these dosimeters will be recorded before e
and after the laboratory session.
For the experiments described, the students are near the neutron howitzer for approximately ten (10) minutes in order to either adjust the position of the liquid scintillator or to slide the sample in or out fo r 1
irradiation.
An estimated total accumulated exposure of 0.2 mrem /hr for the
[
one (1) hour laboratory session can be expected.
This exposure is well below 25% of MPD values stated in 10 CFR-20 and conform to "ALARA" philosophy.
The sealed source is not removed from.the howitzer at any time during the laboratory sessions, periodic surveying of the radiation level around the howitzer immediately outside the port with and without the port plug in place will be carried out and results posted near the howitzer to inform the students coming in to do the experiment.
At the end of each day of use, the howitzer will be surveyed to determine if the neutron source is in the storage position.
When not in use the neutron Source No. N800118 will be stored in the i
storage position of the U.S. Nuclear NR-2 howitzer. The side ports and top closure port will be locked at all times, with the key available only to the laboratory instructors, chairperson of the Physics Department and Radiation Safety Officer.
1 For Source No. M233 which shall remain in storage, the key for the lock is controlled by Dr. Bruce C. Lutz of the Department of Electrical Engineering and available to the Radiation Safety Of ficer for calibration purposes.
a.
Specification of Radiation Safety Responsibilities and Duties i
Although written for NRC License 07-01579019, the University of Delaware Radiation Safety Manual covers all NRC licensed activities at the University of Delaware. The purpose, organization and responsibilities of the University Radiation Safety Committee l
are outlined in Sections 1.1, 1.2 and 1.3 and of the Radiation Safety Officer in Sections 2.1 and 2.2.
Qualifications of the Radiation Safety Of ficer are stated under Section 4 of this application.
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b.
Personnel Monitoring Students in PS 617/618 will wear Bendix Model 884 fast neutron - Y tissue equivalent dosimeters having a detection range of 0-200 mrem for measurement of whole body exposure.
t Other personnel monitoring requirements are covered by Section 3.8 UDRSM. Film badges for whole body f ast neutron - y are supplied by R. S. Landauer, Jr., 6 Company, Glenwood. Illinois on a bi-weekly basis.
I c.
Radiation Safety Program Surveys to be carried out during the PS 617/618 course are
^ described in the paragraphs under Item 6.
In addition the Radiation Saf ety Of ficer surveys the howitzer and storage con-tainer of the two Pu-Be sources on a quarterly basis during leak' testing procedures for n, y radiation levels.
d.
Record Management log of surveys conducted during student experiments will be kept by the course instructor. All other records pertaining to the Pu-Be sources are kept by the Radiation Safety Officer with copies in the Departments of Physics and Electrical Engineering.
+
e.
Scaled Source Leak Testing All leak testing is performed by the Radiation Safety Officer or the Health Physics Technologist under direction of Radiation Safety Officer. Qualificatians of Radiation Safety Officer are stated under item 4.
Leak testing is carried out by smearing the surface of the sources with a cloth smear attached to an 18" forceps.
Smears are counted on an Eberline Model F-1 windowless gas flow detector attached to Eberline Model MS-2 miniscaler rate meter.
Each smear is evaluated by comparison to count rate received on alpha plateau of proportional counter of an Eberline Serial //7422 Pu-239 disk source of 0.0046 uCi + 2% traceable to NBS.
Pu-Be sources are leak tested on a quarterly basis.
i f.
General Safety Instructions A copy of the UDRSM is submitted with this application.
Sections 3.3 and 3.5.2 apply.
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a g.
Emergency and Decontamination Procedures l
These are listed in Section 4.0 of UDSRM and the call list in Section 4.7 is posted in the lab rooms where the Pu-Be sources are kept. The Radiation Safety Of ficer would supervise any problem such as a source rupture which would require decontami-nation.
h.
Procedures for Training of Personnel
- 1) A description of the training for students taking PS 617/618 is described in the paragraphs under item 6.
2)
Source No. M233 is in storage and will be used only for cali-bration purposes in the foreseeable future, but should a project be proposed for its use, the persons who may be involved in or associated s.ith the use of this source must fulfill the requirements of the Radiation Safety Committee for authorization as outlined by the UDRSM. Sections 3.1, 3.2, pages 5-9.
Persons not fulfilling these, requirements may be trained on the job under the direction of Dr. Lutz, this on-the-job training to cover items listed on the Instruction Check-Off List found in Appendix A of UDRSM. Persons trained on the job must pass a written examination covering the radioisotope or radiation device for which they are requesting authorization to use.
Also the Radiation Safety Committee may require persons not fulfilling the requirements to complete the one semester, three credit hour formal course, " Safe llandling of Radioisotopes,"
U-675, taught by the Radiation Safety Of ficer. This course covers items outlined on NRC (AEC) Form 313, Section 8.
In addition an nmendment to License SNM-656 for the specific purpose would be sent to the NRC for approval to use Source No. M233 for the project proposed.
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7.
Period of License Renewal of this license is requested for a five year period.
Sincerely, Edwa A~~T ra b an t',
In.D.
President f,/.
^ pplication Approved A
Department of Physics
'I[O6 'E 7/ ' ' " ' i
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t Cheng-MLug Fou, Ph.D.
Associate Professof of Physics
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L Charles B. Cooper, Ph.D.
h Professor of Physics
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,' b Application Approved Department of Electrient
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Enginee ring Bruce C. Lutz, Ph.D.
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Professor of Electrical Ett'gineering Application prepared by and Approved.for the Radiation Safety Committee enny M. Jol asen,
.S.
Safety Cootainator Radiation Safety Officer
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I UNIVERSITY OF DELAWARE RADIATION SAFETY MANUAL I
I References to AEC in this Manual should be changed to Prepared and Written by:
NRC Jenny M. Johansen, M. S.
Radiation Safety Officer I
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Approved for the Univerg/fy Administration i
I by the Associate Provost of Research Date:
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I DEDICATION I
From its first organization as the Comittee on Atomic Energy I
Activities on August 2, 1957, the Radiation Safety Comittee has continued to serve the University of Delaware community in solving problems of radiation safety in research.
From the " grass roots" comittee of five to it present membership 4
of ten, the committee represents the disciplines of the University engaged in research and development.
In th e pa s t, several members have served not only as a member of the faculty but also as the Radiation Safety Officer.
To those members listed below, the Radiation Safety Comittee dedicates this Radiation I
Safety Manual as a token of our appreciation for their services to the University and the Radiation Safety Comittee.
1957 - 1963 Dr. John H. McClendon 1963 - 1965 Dr. C. Burleigh Cooper 1965 - 1967 Dr. Conrad N. Trumbore 1967 - 1971 Dr. Richard B. Murray 1971 - 1973 Dr. Robert L. Salsbury I
1973 - 1974 Dr. Robert Gagne I
Members of the Radiation Safety Comittee - 1974 :
' I Dr. Robert L. Salsbury, Agriculture, Chairman Dr. Olaf P. Bergelin, Coordinator of Research Dr. C. Burleigh Cooper, Physics Mrs. Sheila Cushing, Nursing I
Miss Jenny M. Johansen, Radiation Safety Officer, Executive Secretary Dr. Bruce C. Lutz, Electrical Engineering Mr. M. D. Machnovitz, Safety I
Dr. Jonathan 11. Sharp, Marine Studies Dr. G. Fred Somers, Biolog;ical Sciences Dr. Conrad N. Trumbore, Chemistry I
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I RADIATION SAFETY MANUAL Table of Contents Section Title Page 1.0.
The Radiation Safety Committee 1
I 1.1.
Purpose of Comntittee 1
1.2.
Organization of Committee 1
1.3.
Responsibilities of Committee 2
1.4.
Appeal of Committee Actions 3
2.0.
The Radiation Safety Officer 3
2.1.
Authority of the Officer 3
2.2.
Responsibilities of the Officer 3
3.0.
University Regulations Governing the Use of Radioactive 5
Materials 3.1.
Procurement of Radioactive Material 5
3.1.1.
Approval of Request for Authorization to Use Radioactive Materials or Radiation Producing Devices 5
3.2.
Responsibilities of Project Supervisor 7
3.3.
Responsibilities of All Users 8
3.4.
Classification of Areas 3.4.1.
Unrestricted Areas 9
3.4.2.
Restricted Areas 9
3.5.
Procedures for Using Radioactive Materials 10 3.5.1.
Unsealed Sources 3.5.2.
Scaled Sources 11 3.6 Transfer of Radioactive Materials 13 3.6.1.
On-Campus Transfers 13 3.6.2.
Off-Campus Transfers 13 3.7.
Disposal of Radioactive Waste 13 3.7.1.
General Considerations 13 3.7.2.
Dry Wastes 13 I
i CONTENTS Section Title Page l
3.7.3 Liquid Waste 14 t
3.7.4 Gaseous and Airborne Wastes 15 a
4 3.7.5.
Biological Wastes 15
.]
j 3.8.
Personnel Fbnitoring 15 E
3.8.1.
External Fbnitoring 15 I
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3.8.2.
Internal Personnel Monitoring 17 "m
4.0.
Radiation E=ergency Procedures 18 l
t 4.1.
Minor Spills 18 4.2.
Major Spills 19 i
4.3.
Accidents 19 4.4.
Injuries to Personnel 19 4.5.
Over-Exposure or Ingestion 20 I
4.6.
Fires 20 4.7.
Call List for Radiation Emergencies 20 Appendix Contents 21 I
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lJ 1<0.
THE RADIATION SAFETY COMMITTEE 1.1.
PURPOSE OF THE RADIATION SAFETY COMMITTEE The purpose of the Radiation Safety Committee of the University of Delaware is the promotion of the best practice in safe handling and use of radioisotopes and radiation producing devices throughout the University campus, regional campuses, affiliated institutions and properties throughout the State of Delaware.
The establishment of a Radiation Safety Committee is required by the federal government before an institutional program for the use of radioisotopes in research and development under a broad scope will be licensed.
Federal and state government regulations concerning radioisotopes shall be implemented by the action of the committee in association with individual radioisotope users, department heads and the admini-stration of the University.
Radiation, as used herein, includes x-rays, gamma rays, alpha and beta particles, high speed electrons, neutrons, protons, and other nuclear particles; but. not sound or radio waves, or visible, infrared and ultraviolet light.
1.2.
ORGANIZATION OF THE RADIATION SAFETY COMMITTEE The Radiation Safety Committee shall be appointed by the Provost or the Associate Provost for Research.
Membership shall consist of faculty or professional staff experienced in handling radioisotopes, the use of radiation producing devices, the practice of radiation protection, or those who have a desire to institute practices of safety in regard to radiation.
These members should include the areas of Agriculture, Life and Health j
Sciences, Chemistry, Engineering, Marine Studies, Nursing, Physics, W
Safety and the Radiation Safety Officer.
The activities of the committee are directed by the chairperson, who is appointed by the Provost or Associate Provost for Research upon recommenda-tion of the committee.
The business of the committee is administered through the Radiation Safety Office which is directed by the Radiation Safety Officer. The Radiation Safety Of ficer is a full-time professional staf f member f rom the Division d
of Safety, appointed by the Associate Vice President for Personnel and Eu Employee Relations, upon recommendation of the Radiation Safety Committee on the basis of the person's experience, education, and qualifications in the area of radiation safety. The Radiation Safety Officer serves as executive secretary to the Radiation Safety Committee.
4.
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Mactings of the committee shall be called by the chairman at his discretion, not less than once per quarter (calendar year) or on petition by any member of the committee.
A quorum of the committee to conduct business shall consist of at least three members plus the Radiation Safety Officer.
I The Radiation Safety Of ficer and the chairman shall conduct the interim business of the committee subject to the approval of the committee at the next scheduled meeting.
1.3.
RESPONSIBILITIES OF THE RADI ATION SAFETY COMMITTEE 1.3.1.
Assume the responsibility for the radia tion safety aspects for I
all University programs involving radioisotopes or radiation producing devices.
1.3.2.
Review and grant permission for, or disapprove the use of, radio-isotopes in any amount or radiation producing devices within :he University from the standpoint of radiation safety.
A simple majority of the committee is required for approval.
1.3.3.
Review and prescribe special conditions, requirements and re-strictions that may be necessary for safe handling or radioisotopes
!l including additional training of personnel and physical examinations 1=
(e.g. blood tes t, urine specimens, etc.) before commencing work with radioisotopes, designation of limited areas of use, proper disposal methods, and procedures to be followed after spills or other radiation accidents.
The committee must approve any project involving radioisotopes or radiation producing devices before it can be initiated.
1.3.4.
Serve as the University's sole liaison with the Delaware State Board of Health and the United States Atomic Energy Commission in matters of registration, licensing, and radiation safety, t
1.3.5.
Receive and review periodic and/or urgent reports from the Radiation Safety Officer regarding:
a.
Results of area monitoring.
b.
Personnel exposures as measured by suitable dosimeters, c.
Accidents in handling, storage or use of radioisotopes.
d.
Loss or thef t of any amount of radioisotopes.
e.
Records of radioisotope procurement and disposal.
g I E 1.3.6.
Recommend remedial action if safe procedures are not being observed where ionizing radiation hazards exist or if these procedures are not in compliance with government regulations. I
I 1.3.7.
Pass judgment in advance of construction of new buildings or remodeling of existing buildings in which the use of radioisotopes or radiation producing devices is contemplated. Written approval is needed from the committee of the proposed building plans.
1 1.3.8.
Keep department chairmen and radioisotope users advised of current rules and recommendations of various gove nment agencies concerned with radiation safety and the safe use of radioisotopes.
1.3.9.
Keep a written record of actions taken in approving or disapproving
.g the use of radioisotopes and radiation producing devices and other lg transactions, communications and reports involved in the work of tl'c committee.
1 1.4 APPEAL OF COMMITIEE ACTIONS Actions taken by the University Radiation Safety Committee may be appealed I
by the staff member or department concerned to the Associate Provost of Research, with the prior knowledge of tte Department Chairman and Dean of the College, i
2.0.
IllE PADIATION SAFETY OFFICER 2.1.
AUTil0RITY OF Tile RADIATION SAFETY OFFICER
,I The Radiation Safety Officer derives his authority from the Vice-President for Employee Relations, Office for Safety Coordination and the Radiation Safety Committee.
The Radiation Safety Officer is a member, and the authorized representative, of the Radiation Safety Committee regarding measures to implement radiation protection and control withR the University.
The Padiation Safety Officer, or his authorized representative, has i
the authority to stop a?1 o rtacions with radioisotopes or radiation producing devices chcre a retential hazard or violation exists.
Resumption of operations mty take place only upon authorization from the Radiation Safety Committee.
t 2.2.
RESPONSIBILITIES OF TIIE FADIATION SAFETY OFFICER I
The Radiation Safety Officer will have the responsibility for ensuring adherence to all regulations issued by or subscribed to by the Radiation I
Safety Committee and will advise and assist the Radiation Safety Committee with regard to the current applicabic regula tions of the United States Atomic Energy Commission, the ULJ ted States Public
!E Ilea th Services, state and local agencies, and all similar codes and
! E regulations.
2.2.1.
Implement the organization, adninistration and nanagement of the Radiation Safety Program of the University of Delaware.
2.2.2.
Interpret regulations which govern the use of sources of ionizing radiation and disseminate information on radiation safety.
I 2.2.3.
Develop and keep up-to-date a manual of Radiation Safety regulations I
and procedures for the University of Delaware.
2.2.4.
Supervise all radiation protection programs and develop and maintain these programs.
2.2.5.
Coordinate the dosimetry service, maintain personnel exposure I
records, and give timely notification of exposures to super-visors as well as individuals exposed.
2.2.6 Review all requests for procurement of radioisotopes to assure I
compliance with limitations for possession and use.
2.2.7.
Procure, receive and arrange delivery and shipment of a 1 radioactive materials coming to or leaving the University.
2.2.8.
Maintain records of procurement and receipt of radioactive I
materials, including non-AEC regulated isotopes and radiation producing devices and machines.
2.2.9.
Supervise the radioactive waste disposal program.
I 2.2.10.
Instruct groups of employees on proper procedures for handling radioactive materials.
2.2.11 Maintain radioisotope disposal records and records of transfer of any radiation producing equipment.
2.2.12.
Conduct periodic radiation surveys and wipe tests in laboratories and storage areas; leak tests on significant sources.
2.2.13.
Conduct alpha scintillation meter surveys when applicabic (e. g.
radium storage areas) and provide instrumentation for overseeing the decontamination of alpha-contaminated areas or equipment.
2.2.14 Conduct surveys on and register all radiation producing equip-ment other than those used to calibrate instruments.
2.2.15.
Perform leak tests on sealed sources.
2.2.16.
Maintain running inventory of radioisotopes, sealed sources, and radiation producing equipment at the University.
2.2.17.
Assume the responsibility for storage of sources and materials not in current use.
2.2.18.
Assume the responsibility for calibration of monitoring and surveying equipment.
2.2.19.
Verify and report to appropriate authorities any radiation incident which may have resulted in injury to, or contamination of, personnel or damage to property.
2.2.20.
Note and take steps in order to correct nuclear and radiation safety problems as well as general laboratory safety problems.
2.2.21.
Perform other duties related or similar to the type described above.
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3.0.
UNIVERSITY REGULATIONS GOVERNING Tile USE OF RADIDACTIVE MATERIALS 3.1.
PROCUREMENT OF RADIOACTIVE MATERIAL 1E All radioactive materials for all University facilitica (including Regional Campuses, Research Farms and other of f-campus locations and properties) shall be procured through the Office of the Radiation Safety Officer.
This includes the so-called " license exempt" l
radioact.tve materials.
An instruction sheet and the Radioactive Material Requisition (Form RS0-1) can be obtained f rom the Radiation Safety Of fice.
Examples of this form and sheet are included in Appendix A.
3.1.1.
APPROVAL OF REQUEST FOR AUTHORIZATION TO USE RADIOACTIVE MATERIALS OR RADIATION PRODUCING DEVICES Approval of an applicant using v..e request form (RSO Form APFT) will be granted by the Radiation Safety Committee on the basis of the applicant's experience and training; proposed use, type, and level of matcrial to be used; facility where the material will be used and the personnel involved.
Request fo rms (ilSO Form APFT) can be obtained f rom the Radiation Safety Officer and should be submitted to the Radiation Safety Officer who will circulate requests to the Radiation Safety Commi t tee.
An example of the RSO Form APFT is included in Appendix A.
The procedure for obtaining approval is:
3.1.1.1.
Submit RSO Form APFT.
(This should normally be sub-mitted by the principal investigator who will be the designated License Permit Supe rviso r. )
3.1.1.2.
Upon receipt of RSO Form APFT, the Radiation Safety Officer will review and evaluate the information given.
The inf o rmation and d
recommendations of the Radiation Safety Of ficer are then distributed W
to the committee.
For all approvals whether temporary or permanent, ti.e coumittee reviews R50 Form APFT using the f ollowing parameters:
a.
Authori: ation of Persannel, RSO Form APFT, Pages 1, 2, and 6.
B Both the designated License Permit Supervisor and other a
personnel on the proje:t (users) are classified into the following categories bzsed on their training and experience:
J Class A.
- Adequate training and extensive experience; has held or W
could hold specific NRC license.
Class B.
- Adequate training and experience.
Class C. - Adequate training end some experience or some training and adequate experience.
Class D. - Some training or experience.
Class E.
- 50 previous t raining; or experience. -
1)
License Permit Supervisor - is usually a prof essir.al staf f or f aculty member having rank of instructor or above or those individuals deemed qualified by the Radiation Safety Committee.
In order to supervise users of a Class D or E category, a License Permit Supervisor must have a Class A or B rank.
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a) A License Permit Supervisor will generally be required to meet a minimum of the following requirements:
a college degree at bachelor's level (or equivalent) in science or g
engineering and at least 40 clock hours of training and g
experience in safe handling of radioisotopes, the characteristics of ionizing radiatior., quantities and units of radiation dose and biological hazards of radiation exposure.
- 2) Authorized Users - are the other personnel working on a project or with a device as designated on RSO Form APFT.
They are usually students (graduate or undergraduate) or employees (post-doctoral fellows, research technicians, etc.).
They may be working on the project of the License Permit Supervisor or car ;ing out independent research for an academic degree under general supervision of the License Permit Supervisor.
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- 3) Other Personnel Specifications -
a)
Persons categorized as Class E users can hold that status only for one (1) month af ter issuance of a temporary permit under the supervision of a Class A or B License Permit Supervisor.
b) The License Permit Supervisor (Class A or B) must be present and give direct supervision when a Class E user is handling radioisotopes or radiation devices.
c)
The License Permit Supervisor (Class A or B)shall give J
instruction to the Class E user not registered for the formal i
m course during his/her month at that status in safe handling of radioisotopes used, rules and regulations of 10 CFR-19, 10 CFR-20 and the University Radiation Safety Manual or request Radiation Gafety Office assistance in giving instruction.
Alao, any other users in categories C and D shall be instructed if specified by Radiation Safety Committee.
d)
Certification that instruction has been given will be sent to I
the Radiation Safety Officer via the " check-off list" which J
can be obtained f rom the Radiation Safety Of fice. The u
Radiation Safety Of ficer will verif y instruction through examination.
e) Upon successful examinacion the Class E user will be promoted to Class D status allowing the person to handle radioisotopes independent of the License Permit Supervisor's presence, but i
still under the License Permit Supervisor's general direction.
f)
Persons successfully completing the formal course on Safe Handling of_ Radioisotopes will be promoted to Class B or C J
f l u users or can be License Permit Supervisors if approved by the i
l Radiation Sa fe ty Committee.
~5a-
,, _ _.- - - -.. ~..-.---
- -.- -..~._ _...,--------- - - -... - - -. - - - - - - -
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J The License Permit Supervisor and other personnel (users) 3 are granted authorization by followf.ng the preceding parameters and that the designated License Permit Supervisor's knowledge and ability are commensurate with the project to be carried f
out, hazards involved, agree to follow all University regula-tions governing the use of radioactive materials and radiation producing devices, and, upon request of_ the committee, submit a history of past occupational and medical exposure or any other special medical requirements (e.g. record of recent
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complete blood test).
i b.
Authorization of Project RSO Form APFT; Fages 3 and 4 Project for which radioisotopes are requested shall be reviewed p
by the Radiation Safety Officer and the Radiation Safety Committee for f easibility based on the information given on pages 3 and 4 of RSO Form APFT.
c.
Authorization of Facility Radioactive materials are to be used only in those facilities which have been approvoi by the Radiation Safety Officer and the Radiation Safety Committee.
Due to size of laboratories, benches or portions of benches within laboratories may be designated as radioisotope use areas and nonuse areas. Use areas must be properly designated with a Radio-J active Material sign or tape around the dimensions of the area.
a The granting of the use - nonuse area designation will be based on the laboratory classification.
- 1) Laboratories will be classified as Type A (High Level), Type B (Intermediate Level), Type C (Low Level) and Type D (Very Low j
Level) according to the type and level of material to be used and the type of usage.
(See Appendix B, Tables 1-3; General l
Requirements for each type of laboratory are listed in Appendix l,
B, Table 4.)
- 2) Monitoring Instruments: Unless specifically exempted by the committee or Radiation Safety Of ficer, each labcratory in which radioactive materials or radiation producing devices are used shall have on hand or readily available in operating condition properly calibrated survey or monitoring instrument appro-a priate to the type and level of ionizing radiation used.
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- 3) Other Radiation Safet) Equipment:
The Radiation Safety l
Com:nittee ray require the use of other special equipment or J
devices that it may determine to be necessary to ensure B
the safe use ri radioisotopes in a g;iven situation. This includes special shielding, handling tools or tongs, alarms and warning devices, air sampling equipment and other such apparatus.
4)
Radioactive waste concainers are required as specified in 3.7.
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- 5) Handling and usan of 50 millicurie a:munts of H-3 (organic compounds) and millicurie amounts of 1-125 and I-313 (non-J contained compounds) shall be confined in a fume hood having l3 a flow rate of at least 100 linear feet per =inute.
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4 3.1.1.3.
ISSUANCE OF AUT110R12ED PERMIT If there are no objections within ten days by the Radiation Safety Committee Members to the information given on RSO Form APFT and the Radiation Safety Of ficer's recomendations distributed, a temporary
]
permit and number are issued by the Radiation Safety Officer.
This I
temporary permit has a number which will be used on all radioisotope i
requests. A permanent permit " Authorization Permit for Use of J
Radioisotopes and Radiation Producing Devices" (RSO Form LP) is
!E issued after review and final approval at the quarterly or special meeting of the full comnittee. The temporary number will be changed l
to a permanent one at that time.
3.1.1.4.
AMENDMENT (S) TO AUTHORIZED PERMITS Anendments will be granted on the same basis as original requests i
for authorization but only the pages of RSO Form APFT concerned with the change need be subni t te d.
n.
Examples of pages to fill out if change applies to:
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1)
New isotopes, same project : Pages 1 - 2 l5 2)
Initial isotopes requested, different project: Pages 3 - 4
)
3)
Change in f acility location of usage: Page 5 4)
Same isotopes, project and f acility, new persennel:
Page 6 3.1.1.5.
RENEWAL OF AUT110RIZAT105 Authorizations will be granted for one (1) year. One month before f
the expiration date the permit holder is requested to submit pages 1 and 2 of RSO Form itPET and any of the other pages needed if amendments
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- o the original application are involved.
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3.2. RESPONSIBILITIES OF LICENSE PERMIT SUPERVISOR Those persons who have been issued permits by the Radiation Safety Committee to use radioisotopes are responsible for the safe use of J
radioisotopes and radiation sources by individuals under their super-l 3
vision.
They are also respansible for:
I a.
Compliance with University regulations for safe handling of radioactive mat erials and NRC regulations 10 -CFR-19 and 10-CFR-20.
b.
Instruction of students and employces under their su;iervision in the use of safety devices and procedures (e.g., wearing o f film badges, l
surveying hands and clothing, s ub.ti t urine or blood samples as re-quired by committee, etc.).
To instruct Class E users during the one month duration as outlined in section 3.1.1.2. 3) a) through f),
}
and instruct all users in rules and regulations outlined in point a j
of this section.
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4 c.
Proper planning o f an experiment or procedure to ensure t'at adequate safety precautions are observed.
d d.
Ccmmunication to the Radiation Saf ety Of ficer of all pertinent B
information regarding changes in their permits.
(e.g., employee, operational and procedures changes, alteration of physical plant, etc.)
a.
Limiting the use of radioisotopes under their permits to authorized users.
4 f.
Maintaining required records of receipts, use, storage and disposal of radioisotopes.
E g.
Preparint; an inventory of radioisotopes on hand every May, b.
Maintain security of radioisotopes in use and in storage.
1.
Receive instruction in radiation safety as determined by the Radiation Safety Officer.
4 3.3.
RESPONSIBILITIES OF ALL USERS Each person who han contact with radioisotopes has a responsibility to:
a.
Ref rain f rom smoking, eat ing, drinking, food preparing and applying cosmetics in radioisotope laboratories b.
Survey hands, shoes, body and clothing for radioactivity and remove all contamination before leaving the laboratory.
4 c.
Check work areas periodically for contamination and keep a written record of results.
Periodically means experiment s involving use of J
radioisotopes continuously over a period of time - survey for con-E taminat ion dail y.
Experiment s involving irregular use of radioisotopes at irregular intervals - survey for contamination on day of initial use and daily while use continues.
Written record of results will be inspected by the Radiation Safety Office.
4 d.
Conduct decentamination procedures when necessary.
J e.
Report immediately to the Radiation Safety Of ficer the details us of spills or othe r accidents involving radiocctivity, f.
Wear the recommended personnel radiation detectors such as film badges and/or pocket ionication dosim?ters and/or thermoluminescent dosimeters (TLD).
g.
Use all recommended protective measures such as protective clothing, respiratory protection, remote pipetting devices, ventilated and shielded glove boxes and hoods.
4 4 - - -.
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h.
Keep personal exposure to radiation at the lowesc possible 1cvel specifically below the maximum permissible does (mpd) levels as stated in 10-CFR-20.101.
1.
Maintain good housekeeping practices in the laboratories.
- j. Label radiation equipment and segregate radioactive waste and equipment to avoid cross contamination.
k.
Maintain security of radioisotopes in use and in storage.
4 3.4.
CLASSIFICATION OF AREAS 3.4.1.
UNRESTRICTED AREAS An area is unrestricted and does not require control measures if:
a.
An individual, continually present in the area, cannot receive I
more than 2 mrem in any one (1) hour, or one hundred (100) mrem in any seven consecutive days, to any' portion of the body, b.
When allowance is made for expected occupancy and time variations in dose rate, no indivJdual is likely to receive more than 500 mrem in a calendar year.
3.4.2.
RESTRICTED AREAS a.
All areas within the Univeralty in which dose levels do not conform to the standards for unrestricted areas shall be
(
restricted and shall be under control of the Radiation Safety Of ficer for radiation safety purposes.
b.
A caution sign - CAUTION RADIATION AREA - shall be prominently I
displayed at the entrance to each restricted area and the individual who has been issued a license permit for work with radioisotopes in each such area shall be responsible for controlling access to this area.
3.4.2.1.
F0 STING OF AREAS AND OTllER LABELING REQUIREMENTS Signs are required by law to denote areas or containers with levels of radiation or radioactivity specified in the following
=
sections.
a.
CAUTION RADI ATION AREA - Any area accessible to individuals in which there exists ionizing radiation at such levels that a major portion of the body of such individuals could receive an absorbed dose greater than 100 mrem in any five consecutive days.
b.
CAUTION ll1Gil RADIATION AREA - Any area accessible to individuals d
in which there exists ionizing radiation at such levels that a 5
major portion of the body could receive an absorbed dose greater than 100 mrem in one hour.
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I c.
CAUTION RADIOACTIVE MATERIALS - Although federal regulations I
exempt certain containers, rooms, etc., containtag radioactive materials less than amounts specified as per 10-CFR-20,203 (e ), (f) and 10-CFR-20 Appendix C, for the p urposes of this manual, all containers, rooms, refrigerators, etc., containing any radioactive materials should have a Caution Radioactive Materials sign, also indication of isotope and amount when I
necessary, in order that all persons are aware of the presence of radioactive materials.
d.
Only signs of the design specified in 10-CFR-20 shall be used.
3.5.
PROCEDURES FOR USING RADIOACTIVE MATERIALS 3.5.1.
UNSEALED SOURCES 3.5.1.1.
PROTECTIVE RULES FOR PREVENTING PERSONAL CONTAMINATION Extreme personal cleanliness and careful techniques are the primary means of preventing contamination and protecting against I
ingestion of radioactive materials.
In order to minimize contamination and prevent entrance of radioactive materials.
into the body,the following rules shall be observed in laboratories where unsealed sources are used, n.
Eating, drinking, food preparation, food storage, application of cosmetics and smoking shall not be permitted in laboratories where radioactive materials are stored or used, b.
Storage of food and beverages is not permitted in the same storage location (refrigerator, etc. ) as radioactive materials.
c.
The use of milk bottles or other food containers for handling or storing radioactive materials is forbidden, d.
Pipetting of radioactive solutions by mouth shall not be permitted.
Remote devices are available and shall be used for such applications.
c.
No experiments with radioisotopes should be undertaken I
until trial runs, complete in every detail, are made with nonradioactive materials.
Such runs should be made until the procedure is reproducible, and improvements incorporated as needed, f.
Any work with materials susceptible to atmospheric distribution (e.g. vaporizing, spillage, dusting, effervescence of solution, or other releaser of radioactive gas) shall be confined in a suitabic hood or glove box.
g.
Personnel shall not be permitted to work with radioisotopes if I
there are open cuts or abrasions on the body.
Extreme precaution must be taken to avoid cuts or puncture wounds, especially when working with materials of high activity or of a high hazard. -
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h.
Care must be exercised when using organic solvents to avoid skin contact with radioactive materials, (Solvents may make the skin more permeable.) Appropriate gloves should be worn for handling radioisotopes, j
i.
Monitoring of hands, feet and clothing is recor. ended especially where large amounts of radioactive materials are 1
being used.
Protective garments should be Icft in the lab-
{
oratory when work is completed or until monitored and found 1
free of contamination.
3.5.1.2.
PROTECTIVE RULES FOR CONTROLLING CONTAMINATION OF LABORATORY FACILITIES AND EQUIPMENT j
(
I a.
Auxiliary containers, blotters, and covers shall always be used where danger of spills and contamination of the person or equipment is possible.
I b.
Contaminated equipment, or equipment that has been used and is suspected of contamination, shall be isolated in designated areas in the laboratory or in suitable storage spaces.
l c.
Tools, equipment and apparatus when used in handling radioactive material, should be placed in non-porous metal trays or pans I
which are lined with absorbent disposable paper. This paper should be monitored and changed frequently, d.
Care should be taken that equipment, not immediately necessary to the operations being performed, is not brought into the working area, c.
Equipment and tools shall be routinely monitored following their use.
No equipment shall be returned to s tock unless it is known to be completely free of contamination inside and out, f.
Contamination shall not be allowed to remain on working I
surfaces or floor unless appropriately shicided. (For purposes of this rule contamination is taken to mean amounts of beta-gamma activity greater than 100 dpm or l
alpha activity greater than 20 dpm as determined by standard 2
I smear test on a surface of 100 cm,)
3.5.2.
SEALED SOURCES 3.5.2.1.
DEFINITION A scaled source is one in which radioactive material is I
permanently encapsulated (in stainless steel, plastic, glass, lacquer or other material) to prevent leakage, and in which the intent is to utilize the radiation emitted rether than the material itself.
l 3.5.2.2.
IlANDLING PRECAUTIONS a.
Sealed sources should not be handled directly with the hands. The use of remote handling tools for sources of high activity is essential to minimize both whole body and I
hand exposure.
b.
Users of sealed sources should monitor themselves routinely I
during periods of work with the sources to assure that source rupture or leakage has not occurred.
I c.
Under no circumstances should a user attempt to repair a ruptured or leaking source.
I d.
In case of devices containing scaled sources, users may use the device only as recommended by the manufacturer.
Sources may not be removed from such devices except in those cases where the devices are specifically designed for usage of I
the source outside of the device.
c.
Repair of devices containing radioactive sa rces is normally I
not permitted when such repair involves those parts of the device containing the source.
The Radiation Safety Officer should be consulted to determine the canditions under which minor repairs or corrections may be at thorized.
3.5.2.3.
LEAK TESTING Unless otherwise exempted by A.E.C. regulations because of low activity, periodic leak tests are required on,all realed
- sources, a.
Such tests will be carried out at intervals not to exceed six months (preferably every three months), except in cases where the A.E.C. has specified otherwise.
b.
Such leak tests,as are required, will be performed by the Radiation Safety Officer or his authorized representative.
I Users are required to make their sealed sources available for such tests at the necessary intervals.
I c.
Whenever leak tests reveal the presence of 0.005 microcuries or more of removable contamination on a scaled source, the source must be immediately removed from further use and steps must be taken to prevent and control the spread of contamination, d.
Leaking sources must either be disposed of ao radioactive waste or returned to the manufacturer for repairs.
t l
3.5.2.4.
CAUTION SIGNS, LABELS AND TAGS FOR SEALED SOURCES I
a.
Any sealed source containing by-product material (as defined by A.E.C.) which is used outside of its shielded container shall be labeled with an attached tag not less than one square inch in size bearing the radiation symbol and words I
" Caution Radioactive Material -- Do Not Handle -- Notify Civil Authorities if Found."
Colors shall be magenta and yellow.
I b.
Sealed sources mounted in devices or shields shall be tagged on the device or shield with Caution Radioactive Material.
Also the nuclide and date of assay shall be included.
Colors shall be magenta and yellow.
I.
v-
I 3.6.
TRANSFER OF RADICACTIVE MATERIALS 3.6.1.
ON-CAMPUS TRANSFERS I
li 3.6.1.1.
Radioactive materials shall not be tre.nsferred from one i
department or laboratory to another without approval by the Radiation Safety Officer, since approval for the use of the I
materials is given only for the original working area.
3.6.1.2.
All transfers between laboratories, or from storage areas to I
working areas, shall be done in such a manner as to minimize the probability of spillage or breakage.
Double containers t
should be used, including suitable shielding, for such transfers.
3.6.2.
OFF-CAMPUS TRANSFERS 3.4.2.1.
Radioactive material shall not be shipped or transferred to or I
from the University without approval of the Radiation Safety Officer.
Approved shipments must be packaged and labeled in accordance with D.O.T. regulations, the A.E.C. regulations or the U.S. Pos tal regulations, whichever is applicabic.
3.7.
DISPOSAL OF RADIOACTIVE WAS.tr.
j 3.7.1.
GENERAL CONSIDERATIONS 3.7.1.1.
Except as specifically authorized by the Radiation Safety Committee, no radioactive materials shall be disposed of directly into the sanitary sewage sys tem, into the atmosphere, or into cold trash baskets (non-radioactive was te).
All radioactive wastes must I
be collected by the user in suitable containers for processing and disposal by the Radiation Safety Officer.
I 3.7.1.2.
Any accidental releases of activity into the environment must be reported immediately to the Radiation Safety Officer.
3.7.1.3.
When unusual problems of disposal arise, the Radiation Safety Officer must be consulted to establish a satisfactory procedure.
3.7.1.4.
The Radiation Safety officer will collect all dry and liquid radioactive waste periodically.
3.7.1.5.
All types of waste should be separated by half-life, short (less than 30 days), and long (more than 30 days).
3.7.2.
DRY WASTE 3.7.2.1.
CONTAINCRS Waste containers for disposal of dry contaminated wastes are to I
be available in all laboratories using unsealed radioisotopes.
Normally these should be a metal waste container with a step-pedal operated lid and plastic bag liner.
Was te cans should be conspicuously labeled with a caution Radioactive Materials sign.
I
I I
3.7.2.2.
SEGRECATION LY IIALF-LIFE Dry waste, contaminated with short-lived radioactivity (half-life is less than 30 days) should be collected in a separate I'
container from dry waste contaminated with long half-life (greater than 30 days) material.
Normally the short-lived material vill be held for 10 half-life I
periods and then disposed of, according to procedures of the Radiation Safety Officer, as non-radioactive vaste.
3.7.2.3.
LABELING OF WASTE FOR PICK-UP BY RADIATION SAFETY OFFICER All dry radioactive waste for pick-up by the Radiation Safety Officer shall be sealed and properly labeled with a standard radioactivity caution label and should bear the following j
additional information:
a.
User's name, department and account code number b.
Isotope (s) c.
Approximate quantity of activity d.
Date 1
3.7.3.
LIQUID WASTE 3.7.3.1.
CONTAINERS Containers for liquid waste should be 5 gallon plastic carboys or 30 gallon liquid drums, filled with solid pak, of the type lI provided by Teledyne/ Isotopes.
3.7.3.2.
LABELING OF WASTE FOR PICK-UP BY THE RADIKfION SAFETY OFFICER lI All liquid containers shall be properly labeled with a Caution Radioactive Material sign.
In addition, liquid waste containers shall bear the following additional information; a.
Users' names, department, and account code number b.
Isotope (s) c.
Approximate quantity of activity d.
Date I
'rinciple solvents or reagents in container (e.g. water, acid, e.
etc.) includine approximate pH.
3.7.3.3.
STRONG ACIDS, BASES, OR OTHER SOLVENTS Unless special arrangements are made with the Radiation Safety Officer, the user is required to neutralize or otherwise dilute strongly acid or basic waste solutions to the point that they I
can be reasonably mixed in solidifying or absorbing agents I
without causing violent chemical reactions or releasing strong fumes and vapors or volatilization of the isotope to gaseous state.
I In case of organic solvents, especially those which may be highly volatile or otherwise reactive, appropriate precautions must be noted on the waste containers.
3.7.4.
GASEOUS AND AIRE 0RNE WASTES In cases where the release of volatile radioactive products or radioactive acrosols are anticipated, means should be provided to trap such materials (either by chemical or physical methods). The resulting product may then be handled as a liquid or dry waste which ever is appropriate.
3.7.5.
BIOLOGICAL WASTES The Radiation Safety Officer should be contacted regarding all prob 1 cms that may arise in disposal of biological wastes containing radioisotopes.
3.8.
PERSONNEL MONITORING 3.8.1.
EXTERNAL MONITORING 3.8.1.1.
A.E.C. REQUIREMENTS Any person working with radioactive material under the University's A.E.C. license is required to wear a personnel dosimeter whenever entering a restricted radioisotope area where he may be likely to I
receive a dose in any calendar quarter in excess of 25 percent of the values stated in 10-CFR-20.101.
Maximum Permissible Dose in Rems / calendar quarter CFR-20.101 Whole body, head & trunk active blood-forming organr, lens of eyes or gonads 1.25 Rem I
Hands, forearms, feet & ankles 18.75 Rem Skin of whole body 7.5 Rem 3.8.1.2.
UNIVERSITY REQUIREMENTS In addition to the A.E.C. requirements personnel dosimeters I
ar" required for University personnel for all the following situations except as specified in part 3.
I tters of an energy exceeding 0.25 Whenworkingwithbetaem{C,3S a.
3H,1 S and 45Ca unless specified MeV (i.e. excluding by the Radiation Safety Office.)
b.
When working with x-ray and gamma emitters of any energy.
c.
When working with neutron sources of any type.
I I
i d.
When working with x-ray producing devices, e.
When working with accelerators or devices used for accelerating chargcd particles.
3.8.1.3.
EXEMPTIONS FROM PERSONNEL MONITORING I
Personnel dosimeters may not be required in cases where it has been definitely established by the Radiation Safety Office that external exposure will not exceed the specified limits.
Exemptions will depend on the intensity and energy of the radiation and I
working conditions involved.
3.8.1.4.
DOSIMETER INFORMATION a.
The Radiation Safety Office issues film badges to individuals who require them.
Individuals must fill out a Request for i
Personnel Dosimeter form which is available in the Radia tion Safety Office.
b.
The badge, when required, must be worn at all times when I
the individual is occupationally exposed.
It should be worn in a fashion so as to indicate whole body exposure (breast pocket, collar, or belt) except in the case of ring, wrist or ankle badges, c.
Badges are issued once per month in the case of beta-gamma badges and twice per month in the case of neutron badges, d.
The badge is not to be worn when the individual is under-going diagnostic or therapeutic radiation exposure, e.
When not in use the badge should be stored in a location away from radiation (above background), excessive heat or
- moisture, f.
Badges that are not returned to the Radiation Safety Office I
by noon of the secons working day after the badge change date shall be considered LATE. The individual will be charged a late fee af $2.00 for a late badge.
Badges that are not returned to the Radiation Safety Office within two weeks
'I after the film badge change date will be considered LOST.
The individual will be charged $4.00 for each lost or damaged film badge, g.
If the film badge is lost or damaged, the maximum legal exposure must be entered on the individual's radiation exposure I
record unless the individual's Report of Missing Dosimeter shows evidence of no possible exposure.
Therefore, it will be to the individual's advantage to return " lost badges" that have been found so that his exposure may be determined.
3.8.1.5, RECORDS AND REPORTS I
a.
Permanent records of film badge exposures are maintained by the Radiation Safety Office.
Copies of these reports are m u
r
4..
distributed monthly, by department, to all departments having monitored individuals.
b.
In cases where individual monthly doses exceed 100 millirem, the Radiation Safety Of fice will notify the individual through a written Radiation Exposure Report. The individual shall fill out the information requested on the report and return it to the Radiation Safety Of fice so that recommenda-tions can be made to prevent recurrence of exposure.
c.
The Radiation Safety Of fice will provide an individual, upon written request, a copy of his permanent occupational exposure
=
history.
Records of exposure will be forwarded to new employers upon written request of the individual.
3.8.2.
INTERNAL MONITORING OF PERSONNEL 3.8.2.1.
ROUTINE URINE ANALYSIS License Permit Fupervisors and users qualified to handle and use in 4
an experiment millicuric amountc of H-3 (organic compounds), Iodine-125 and Iodine-131 in noncontained form, alpha emitters or such other materialo that the committee may specify are subject to routine urine analysis in accordance with the following parameters:
a.
Each person so qualifled shall submit a urine sample to the Radiation Safety Of ficer who will assay the sample. Also, each person shall upon the Radiation Safety Committee's request submit a recent record of a complete blood count and any other medical history necessary including a physical examination. Any J
previous radiation exposure history must be filed with the W
Radiation Safety Officer.
b.
Any person handling and using in ar. experiment 50 millicuries of H-3 (organic compounds) or 10 mil 11 curies of lodine-125 and/or Iodine-131 (noncontained forms) shall notify the Radiation Safety Of ficer at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in advance of such usage and submit a urine sample fc-bioass'y. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after handling and using in an experiment 50 millicuries of H-3 (organic compounds),
the person shall again submit a urine sample to the Radiation Safety Of ficer for bioassay.
Such conditions shall apply for Iodine-12 5 and lodine-131 (r.3ncont ained forms) except that a urine sample will be required after handling and using in an experiment 10 millicuries within 24 to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
l c.
Personnel who will be handling and using in an experiment l
microcurie amounts which are drawn f rom stock supplies containing 50 millicuries o f H-3 (organic compounds) and 10 millicuries of I -3 25 o r I-131 (noncontainea forms) on a continuous basis, shall supply a weekly urine -
to the Radiation Safety Of fice for bioassay.
d.
Personnel using microcurie amounts of H-3 (organic compound? and I-125 and Iodine 131 (noncontained forms) will be requested to submit a urine sample for bicassay before starting and again upon te_rmination of the research project.
4 1
4 E.
Per sonnel using any other materials the committee may j
specify shall have routine urine analysis at time intervals W
designated by the Radiation Safety Officer or when gross contamination levels in the laboratory they work in show incidence of improper handling.
3.8.2.2.
SPECIAL URINE ANALYSIS Individuals who are known or suspected to have accidentally J
swallowed, inhaled, absorbed, or otherwise ingested radioactive lu materials will be required to submit urine specimens to the l
Radiation Safety Of ficer for analysis. Tae number and frequency of such samples will be established by the Radiation Safety Officer based on type and level of material and condition of intake.
l 3.8.2.3.
ANALYSIS OF OTilER EXCRETA Depending on the particular radionuclude, its chemical and physical form and the mode of intake, the Radiation Safety Office is authorized to require the submission of other excret'. (such as fecal samples, nose wipes, or breath samples) in addition to or in lieu of urine samples.
3.8.2.4.
W110LE BODY COUNTING In the case of real or suspected intake of gamma emitting nuclides, whole body counting may be required in addition to or in lieu of excreta samples. The Radiation Safety Officer will arrange such p ro ce d u re s.
1 4'
4 4
4
-17a-
I I
4.0.
MDI ATION EMERGENCY PROCEDURES Emergancies resulting from accidents in isotope laboratories may I
ran e f rom minur spills of radioactivity, involving relatively no o
personal hazard to major radiation incidents and spills, involving extreme hazards and possible bodily injury.
Because of the numerous I
complicating facters which may arise and because of the vide range and variety of hazards, set rules of emergency procedure cannot be made to cover all possible situations.
In any emergency, however, the primary concern must always be the protection of personnel from radiation hazards. The secondary concern is the confinement of the contamination to the local area of the accident if possibic.
The following procedures are regarded as recormnendations except those with asterisks (*) which are required.
REMEMBER ALWAYS TO STATE:
TYPE OF RADIATION EMERGENCY YOUR NAME I
WHERE EMERGENCY ASSISTANCE IS NEEDED WilEN CALLING TliE RADIATION SAFETY OFFICER OR SECURITY,IF RADIATION SAFETY OFFICER CAN NOT BE REACHED.
4.1, MINOR SPILLS IN UNPROTECTED AREAS INVOLVING SO RADIATION HAZARD TO PERSONNEL (IN ANY AMOUNT)
I
- a.
Noti:'y all other persons in the area immediately.
I b.
Permit only the minimum number of persons necessary to deal with the spill into the area.
c.
Confine the spill irmnediately.
- d.
Notify the RADI ATION SAFETY OFFICER as soon as possible. (2)
!g
- e.
Pe rmi t no one to resume work in the area until approval of the lg RADIATION S/EETY OFFICER is secured.
l (1) Water may be used except when chemical reaction v'.th water would I
generate an air contaminant.
Oil should then be used.
(2) The RADIATION SAFETY OFFICER (or an assistant) may be reached directly by using; the emergency call list posted in each radioisotope laboratory.
I Or, call the Campus Security Office number directly and they will locate assistance.
18-
I 4.2.
MAJOR SPILLS - INVOLVING RADIATION HAZARDS TO PERSONNEL
- a.
Notify all other persons in area immediately of hazard.
- b.
Request all persons not involved in the spill to vacate the room at once and notify the RADIATION SAFETY OFFICER immediately giving details of spill. (2) c.
Make no immediate attempt to clean up the spill. (3)
I d.
If spill is on skin, flush thoroughly with water.
If the spill is on clothing, discard outer clothing at once.
c.
Switch off all fans, f.
Vacate the room and prohibit entrance to contaminated area.
I
- g.
Permit no person to work in area until the approval of the RADIATION SAFETY OFFICER is secured.
I h.
Under no circumstances should an untrained person attempt to examine or clean up the radioactive material.
4.3.
ACCIDENTS - INVOLVING RADIOACTIVE DUSTS, MIST, FUMES, ORGANIC VAPORS I
AND GASES
- a.
Notify all other persons to vacate the room immediately.
b.
Hold breath and close all windows and escape valves.
Switch off air circulating devices if time permits, c.
Vacate the room.
- d.
Notify the RADIATION SAFETY OFFICER at once.(2)
I c.
Ascertain that all doors giving access to the room are closed and locked.
If necessary, post guards to prevent accidental opening of doors.
- f.
Do not reenter the room until approval of the RADIATION SAFETY OFFICER is secured.
4.4.
INJURIES TO PERSONNEL - INVOLVING RADIATION HAZARD I
a.
Wash minor wounds immediately (within 15 minutes if possible) under running water while spreading edges of gash.(Note: light tourniquet action to stop vinous return bit not to restrict arterial flow may be desirable to stimulate b1 ceding.)
b.
Notify the RADIATION SAFETY OFFICER or Security for Special Medical Assistance.
(2) The RADIATION SAFETY OFFICER (or an assistant) may be reached directly I
by using the emergency call list posted in each radioisotope laboratory.
Or, call the Campus Security Office number directly and they will locate assistance.
(3)
If spill is liquid and hands are protected, right the container.
I I
c.
Permit no person involved in a radiation injury to return to work without approval of the RADIATION SAFETY OFFICER.
4.5.
OVER. EXPOSURE OR INCESTION I
- e.
Any person who suspects over-exposure to radiation from any source must report immediately, by phone or in person, to the
proved:
Chairman, Radiation Saf ety Cornittee 1
. _ _ - _ _ - _ - RSO Form - APFT FACILITY APPROVAL 1.
Department
- 2. Building 3.
Room j
4.
Sketch of Facility:
I I
I 5.
Type of flooring:
6.
Walls and Ceiling: (Paint or coating) 7.
Bench top material:
8.
Hood (s) Single ducted?
Yes No: Flow rate sash linear ft/ min 9.
Number of persons normally working in area:
Education IcVel of persons in area under-grad /
grad /
technician /
postdoct/
110.
or faculty?
Are other personnel approved radioisotope workers?
Yes No.
Is this area also used for study / office area for research personnel?
I.Monitoringdeviceinfacility:
11 Yes No.
(If yes and haven' t listed device in project proposal list make, model, type, range.)
I 12.
Special handling facilitics (shielding, glove boxes, etc.)
I 13.
Staff member in charge of laboratory:
L4.
Individual submitting this request:
Date l
~
I Approved:
Date:
Radiation Safety Officer I
I
l RSO Form - APFT I
STATEMENT OF TRAINING AND EXPERIENCE 1.
Name
- 2. Social Security No.
3.
Type of Training (Circle Yes or No in Columns I and II.
If "Yes" is indicated in either column, complete items III and IV)
TYPE gg ON THE JOB MIERE TRAINED D
ION (A) Principles and Practices l Circle Ond l Circle Onel of Radiation Protection Yes No Yes No (B) Radioactivity Measurement l_ Circle Onel l Circle Onel monitoring techniques, and instruments.
Yes No Yes No (C) Mathematics and calculations Wir 1 une[
l Circle Onel basic to the use and meas-urement or radioactivity.
Yes No Yes No (D) Biological effects of Nircle Onej l Circle Ond radiation.
Yes No Yes No 4.
Formal Courses (If "Yes" circled in column I for any of items above, complete this item, listing all courses pertaining to use of radiation or radioactive materials, atomic and n'1 clear structure, radiochemistry, radiation biology, nuclear engineering, etc.)
litic of Course Wilere Trained Course Content (A)
(B)
(C)
(D) 15.
Experience (Lis t actual use of radioactive materials, details of formal laboratory courses or on the job training.)
Isotope Maximum Amount Where experience Duration Type of use I
I 6.
Was film badging required in experience situations?
Yes No 7.
Additional Comments or Remarks:
I I
E-RSO Form - Lp UNIVERSITY OF DELAWAgg I
AUTIIORIZATION PERMIT FOR USE OF RADIOISOTOPES AND RADIATION PRODUCING DEVICES License Permit Number.
Licensce:
Date issued:
Expiration Date:
NOTE:
License Permit number must be shown on all radioisotope orders in space provided for License Number.
In accordance with statements and representations made in your Request for Author-ization to use Radioactive Materials or Radiation Producing Devices, dated approval is hereby granted authorizing the below named individuals to order, possess and I
use the materials or items designated below in accordance with University regulations and such other conditions as are herein specified.
1.
AUT110RIZED USERS:
l Nnmo l
Dopartmont l
Status l
I I
I 2.
LOCATION (S) 0F USE:
l Buildinn l
Rnom l
Comments l
I I
3.
AUTHORT7ED RADTOISOTOPES OR ITEMS:
Maximum Acitvity Limits
{
n*
Team
~Per Fvneriment l
Per Order l
Possession (Storage) }
Nor14dn I
I AUT110RIZED USE:
4 I
I I
il
'W 5.
CONDITIO!!S:
i Laboratory Monitors:
Film Badges:
Other Dosimeters:
I Caution Signs:
i i
Waste Containers:
Personnel Restrictions:
Special Precautions or Requirements:
I I
' I Approved:
Date:
Chairman, Radiation Safe ty Coc:mi ttee I
I I
F i
b I
1 I
. I
'd
.---,_n
---,...w.~
..,.,-w-,,..
,vvy--.
,-m.,-,-..,-.
Tills FORM llSEI) FOR ONIN 1 OUR FORMS OF SAME NUCl II)E Control RADIOACTIVE MATERIAL REQUISITION I University of Iklaware N "-
Note: Complete a separate requisition for each different Nuclidet retain top sheet and forward Forrn RSO-l remaining form to Radiation Safety Officer at 417 Academy Street.
I Department User Phone Project Account or Grant Number 1.icensee License Number i
Quantity (mci)
Catalog No.
Nt de and Form Specific Act.
Est. Price I1.
1.
1.
1.
1.
2.
2.
2.
2.
2.
3.
3.
3.
3.
3.
4.
4.
4.
4.
4.
M Total Vendor Suggested Dates Desired Remarks I
l Requested by Building Date of this Request Approved by (Department head or authorized agent)
Date I
--Do not write below this line- - -
Approved by R.S.O.
Date Comments lI (To be completed when order received) l l P.O. Number Date Received User Notified
[] A.M.
I
[] P.M.
l Assay Information llealth Physics Survey Billing I Quantity (mci) i Exposure Rate-unshielded i
Cost of Nuclides i
C l
f l
f one. (mci /ml)
Vendor llandling Vol. or Wt.
l l
{
Exposure Rate-shicided Freight, postage, etc.
Sp. Act.
e i
l Time of Assay l
Other charges Surf ace Contamination Total Solids
{
abiha:
Normality l
{
{
beta.eamma:
Total Purity
{
{
l l
Other precautions Date Billed I
Lot No.
l l
l l
Billing Prepared by:
Ser. No. (scaled source) l l
l l
l l
l l
Journal Voucher No.
l fOther i
i 1
l 5 Received fly:
Date t I
I UNIVERSITY OF DELAWARE RADIATION SAFETY OFFICE REQUEST FOR PERSONNEL DOSIMETER Badge No.
All of the information requested below is required by the Atomic Energy Commission.
If this requisition is not complete, it will be returned.
No badge will be issued without a completed requisition.
- 1. Name
- 2. Maiden Name Last, First, Middle (Please Print)
- 3. Sex
- 4. Social Security No.
- 5. Birthday Month-Day-Year
- 6. University Location Department Building Course Work Employee
- 7. Status Faculty, Staff, Student
- 8. Will you be working with x-rays; radioisotopes; other?
If other circle one:
accelerator ;
reactor ;
gamma irradiator ;
neutron source?
- 9. IInve you previously been associated through employment or course work with an employer or University etc. where you were required to wc ar a dosimeter (film badge, TLD, pocket ionization chamber,etc.).
Do not include any diagnostic or therapeutic radiation exposure.
List most recent employer first.
Employer & Address Started Terminated A.
I i
B.
l C.
I l
D.
- I Signature of Requester Signature of Radiation Safety Officer
UNIVERSITY OF DELAWARE RADIATION SAFETY OFFICE RADIATION EXPOSURE REPORT I
Date l
l I
It has been reported by the personnel dosimetry service that the dosimeter worn by
, dosimeter number for has received a total dose of millirems.
The dosimet.y service additionally reported I
- 1) Reason for exposure - check appropriate reason (s):
Exposure due to x-rays or radioisotopes.
Adequate protection devices not available.
I U
Failure to use protection devices.
C Badge exposed while it was not being worn.
Badge partially destroyed by heat, water, light, or time.
None of the above, explain below.
Unknown.
- 2) Explain all reasons checked in Item 1.
I Recommendation of Radiation Safety Of ficer to prevent recurrence of exposure; I
Signature of Employee Signature of Radiation Safety Officer f
I UNIVERSITY OF DELAWARE RADIATION SAFETY OFFICE I
REPORT OF MISSING DOSIMETER Date Name Badge #
Date of Missing Badge I
The dosimeter described above has not been returned to the Radiation Safety Office.
In order to keep adequate radiation exposure records as required by the Atomic Energy Commission and the State of Delaware, the badge must be returned to the Radiation Safety Office.
I If the dosimeter is available, return it with this form to the Radiation Safety Office.
If the dosimeter is not available, answer the following questions and return this form immediately to the Radiation Safety Office.
I 1)
Reason dosimeter was not returned.
I
- 2) Type of radiation to which you were exposed during the month in question.
If you were working with radionuclides, please list them.
I
- 3) Vacations during the month in question. Give dates.
- 4) Any unusual known radiation exposure during the month in question.
I i
Signature of Dosimeter Wearer ACTIONS OF THE RADIATION SAFETY OFFICE I
I Date Signature of Radiation Safety Officer,
I UNIVERSITY OF DELAWARE NEWARK. DELAWARE 19711 I
OFFICE FOR S A FET Y COORDIN A TION i
l 417 A C A DEMY ST REE T PHON E: 302.786 8475 I
Radiation Safety Officer I
Dear Sir:
I
_, Social Security Number birth date
, has indicated that he/she was associated with your institution in a capacity which required radiation monitoring.
This association existed from to We would appreciate receiving a summary of those occupational exposures to add to our records.
Thank you.
I I
Jenny M. Johansen, M.S.
Health Physicist
.E Radiation Safety Officer
'E University of Delaware STATEMENT Under the provisions of 10 CFR 20.404, I authorize the release of and request that all my radiation exposure records be furnished to the Radiation Safety Office.
I Signature Date I
I
UNIVERSITY OF DELAWARE NEWARK. DELAWARE 19711 I
O F FIC E FO R S A FE T Y COORDIN A TION 417 A C A D EM Y S T R E E T 302.786 8475 I
PHONE:
I Radiation Safety Officer I
I
Dear Sir:
I The radiation exposure information you requested on Social Security Number
, birthday is as follows (readings given in mrem):
Year Type of First Second Third Fourth Totcl for Radiation Quarter Quarter Quarter.
- Quarter, Year I
I I
I This report is furnished to you under the provisions of the Atomic Energy Co:maission regulations entitled " Standards for Protection Against Radiation" (10 CFR-Part 20).
You should preserve this report for future reference.
Sincerely, I
Jenny M. Johansen, M.S.
I 11ealth Physicis t Radiation Safety Officer University of Delaware I
I
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I RAD 1ATION SAFETY 0FFICE Instruction Check-off List This is to certify I have instructed:
I lGraduate Student I
l Undergraduate Student l
l Employee I
in the proper procedures of handling radioisotopes that he/she will be using; that this instruction included:
l
} Storage areas f or radioisotopes in my lab.
l l Areas of my lab where radioisotopes can be used.
l l Type (s) of radiation f rom isotope (s) used.
j l Energy of radiation from isotope (s).
l l External and internal hazards f rom isotope (s).
l l Special problems of handling the isotope (s).
l l Review of Federal Regulations 10 CFR-19.12,19.13.
l
) Discussion of Federal Regulations 10 CFR-20.
l l Sections 3 and 4 of University Radiation Safety Manual, pages 5-20 and Appendix.
]
l Security measures to be used when using radioisotopes or storing them.
Upon successful completion of examination by the Radiation Safety Office, I requent a Class "D" user status for this person.
I Permit Supervisor I
I Re turn to :
Radiation Saf ety Of fice, 417 Academy Street within one (1) month of receipt.
I
1 1
}
I Form RSO 2 U f41 VE RSI TY OF DELAWARE R ADI ATIOf4 EXPOSURE RECORD i
8ADGE NUMOE R I NAW (L A S T.
FI RS T. Mf)
(M AIDE N N AME)
I STATUS DEP A RTMENT I
IalATH I
OATE OF SOCIAL lOATE DATE LEC8)ntTv NO 15TAATED TERMIN A TE D WHOLE BODY GAMMA & LRAY MREM O
IEAR BETA OR LO%, X-RAY MREM NEUTRON zy YEA ALY QUARTERS YEARLY CumulaNe VEAALY QUA4TERS YEAALY Cumutative h
1st 2nd 3r a Afh I
15t 2M Jrd 4th rev.
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PREVIOUS RADIATION EXPOSURE PCRICO COVEREO PERIGO COVEHED
. ATURE OF WOR K IMPLOYER NATUAE OF WOnK EMPLOYER I. QTAL E xoOSU AE (M REV).-
OORESS ACORESS I
l TOTAL h /POSURE 8M HEY) - C4 nma & a B
Gammi L n 8
'ERIOO COVE F F O PEnlOD COVE Af D AT')R E OF WORK NATURE OF WOPK 5VOLONER E MPLO /E A laonEss j
ADOeEss I
i T OT AL EXPO 5U A E (MRLM) - Camma t =
0 TOTAL E x t'OSU R E (M A E U) - Ga n na in O
IiTunE Or wOuK
]PcR.oDcost9EO niOO cOvtnEO N Arunt Or Aonx i
9LOYER I
EMPLOYER l
hADOnEss
- OnEss
.o4 ITAL EXPOSURE (MREV} -
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G a m.n a & a O
COMMENlS I
I I
APPENDIX B EXPLANATIONS OF TABLES I, II, III AND IV Laboratories are classified based on three factors: (1) radio-I toxicity hazard of nuclides in use; (2) maximum amounts of activity stored or used in the area; and (3) type of use in terms of relative hazard of the handling procedures.
In Table I, radioisotopes are classified as to their relative radiotoxic hazard in relation to internal dose.
The hazard of a radio-isotope depends on the ef fective half-life of the nuclide in the body I
or organ, the type and energy of the emitted radiation, the physical and chemical form of the material, and the organ of maximum concentration.
For normal usage, laboratories are classified according to the total activity of the various classes of nuclides present in the lab.
Table II gives the four laboratory classifications (high, intermediate,
I low, and very low) based on the hazard group and activity present.
In cases of more than one nuclide in use in a laboratory,the classification will be determined by a summing of the constituent nuclides.
The amount of nuclide permitted in a given class' laboratory may be increased or decreased according to type of usage.
With high accident risk operations, the amount permitted within the classification is decreased.
For simple, relatively safe operations, the amount in a given classification may be increased. As a guide, the modifying factors in Table III are used to determine the amount by which the permitted activity should be increased or decreased.
The Radiation Safety Committee does not have rigid specifications on design requirements for various classes or radioisotope laboratories.
I As guidelines, however, the design criteria set forth in Table IV may be used.
In designing new areas the researcher should consult the Radiation
(
Safety Officer to discuss requirements for a particular facility.
EXPLANATION OF TABLE V As per section 3.7.1.1., specific authorizations can be given I
for disposal of waste via sanitary sewer.
In Table V, the federal guide-lines cre stated to insure that, based on the University water flow rate, concentrations of trace amounts cr radioactivity released to the sanitary I
sewer under a specific authorization from the Radiation Safety Committee would not exceed the guidelines as stated in 10-CFR-20.
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APPENDIX B I
Table I Suggested Radioisotope Classification (Unsealed Sources)
I Class Description Examples
- I Very High Hazard S r-90, Po-210, Pu-2 3 9 II High Hazard Ca-45, I-131 III Moderate Hazard P-32, S-35, Co-60, Rb-P.), Cs-137 IV Low Hazard H-3, C-14
- Radiation Safety Officer has a more complete list of examples.
Table II Suggested Laboratory Classification (Considering Table IV & I)
Radioisotope Lab Crade Class A (High)
B (Inter)
C (Low)
D (Very Low)
I 1 mci up to 1 mci up to 10 uCi up to 0.1 uCi I
II 10 mci 10 mci 100 uCi 1 uCi III 100 mci 100 mci 1 mci 10 uCi IV 1000 mci 1000 mci 10 mci 100 uCi I
lg Table III 3
Modification Factors for Laboratory Clausification (Table II)
Use Factor Storage only X 100 Simple Wet Operation (e. g. preparing stock solutions)
X 10 Normal Chemical Operation (e.g. analysis)
X1 Complex Chemical Operation with High Risk of Spill X 0.1 Simple Dry Operations (e.g. work with volatile compounds)
X 0.1 Dry Dusty Operations (e. g. grinding)
X 0.01
'I l
l
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TABLE IV SUGGESTED GENERAL DESIGN SPECIFICATIONS FOR 1ABORATORIES USING RADIOISOTOPES Lab Classification A
B C
D i
Floor Smooth, non-porous Same as A Smooth non-Any l
Easily removable absorbent Protective underlayer No cracks 1
Walls Smooth, non-porous Same as A Painted; smooth Any Strippable if possible Work Benches Smooth, nonabsorbent Same as A.
Smooth sealed Any - cover with Removable covering coating - Cover absorbent paper (as absorbent paper) with absorbent paper.
Ventillation No recirculated air Room under net Room under net Any Absolute filters in negative press-negative pressure, exhaust Air room under ure-Absolute fil-net negative pressure ter recommended Hoods Singularly ducted Same as A Singularly ducted Any Absolute filter Filters optional Flow rate: 100 +
Flow rate: 100 linear feet per minute linear feet per minute Other Consider: Build in shields Same as A Portable, localized Special llandling Devices shielding as needed Glove Boxes m
I Detailed considerations found in:
1.
NBS Handbook 92 " Safe IIandling of Radioactive Materials," United States Government Printing Office, Washington (1964).
l l
I I
i APPENDIX B TABLE V Factors for granting authorization to dispose of radioactive materials via sanitary sewer l
l As per A.E.C. regulations: No licensed material shall be discharged into sanitary sewerage unless it is:
- 1) Solubic
- 2) If diluted by water flow rate to sewer, concentration of material does not exceed that stated in Appendix B, Table I, Column 2 of 10-CFR-20 or;
- 3) Ten times the quantity of material stated in Appendix C or;
- 4) GROSS QUANTITY OF ALL LICENSED MATERIAL RELEASED TO SEWERAGE DOES NOT EXCEED 1.0 CURIE PER YEAR.
I University water flow rates from July 16, 1973 to July 15, 1974 equaled 31,094,030 ft3/ year.
Equaled 85,189.12 ft3/ day /90 buildings divided by 3.53 x 10-5 3
ft /ml -
26,813,000 ml/ day / building.
I Example of Soluble Material Appendix B Appendix C 3-Hydrogen 1 x 10-luCi/ml 1,000uCi 14-Carbon 2 x 10-2uci/ml 100uci I
35-Sulfur 2 x 10-3uci/ml 100uci 32-Phosphorus 5 x 10-4uCi/ml 10uCi 109-Cadm'ium 5 x 10-3 ci/ml 10uci u
I I
I I
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REFERENCES 1.
LICENSING GUIDE FOR TYPE A LICENSES OF BROAD SCOPE FOR LESEARCH AND DEVELOPMENT.
U. S. Atomic Energy Commission, Directorate of Licensing Materials Branch, Washington, D.C.-February, 1973.
I 2.
RULES AND REGULATIONS - TITLE 10, CHAPTER 1, CODE OF FEDERAL REGULATIONS, Part 20, 30, 31 and 33.
U. S. Atomic Energy Commission.
3.
NBS llANDB00K #73.
" Protection Against Radiation From Scaled Sources" -
July, 1960.
4.
NBS IIANDBOOK #53.
" Recommendations for the Disposal of Carbon-14 Wastes-
January, 1957.
I 5.
NBS HANDB001c #48.
" Control and Removal of Radioactive Contamination in Laboratories" - January, 1957.
6.
NCRP REPORT No. 39.
" Basic Radiation Protection Criteria," January, 1971.
7.
" RADIATION SAFETY MANUALS'.' Auburn University - April, 1972.
liarvard University - June, 1972.
New England Deaconess Hospital - 1973.
Peter I
Bent Brigham Hospital -January, 1969.
Iowa S tate University - March,1969.
North Dakota State University - April, 1962.
Ohio State University - 1967.
Purdue University - January, 1972.
8.
NBS HANDBOOK #92.
" Safe Handling of Radioactive Materials" - March, 1964.
II g
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) PSEG Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/622-7000 October 3, 1978 Mr. Boyce H.
Grier Director of USNRC Office of Inspections.and Enforcements Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 78-62/03L l
Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 78-62/03L.
This report is required within thirty (30) days of the occurrence.
Sincerely yours,
.v% g.,
i j
Librip$f F. P.
General Manager -
Electric Production l
l CC:
Director, Office of Inspection and Enforcement (30 copies)
Director, Office of Management Information and Program Control (3 copies)
%0hIkM fCO2 f YYO
Report Number:
78-62/03L Report Date:
10/3/78 Occurrence Date:
9/13/78 Facility:
Salem Generating Station
{
Public Service Electric & Gas Company l
Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
l No. 12 Reactor Coolant Flow Channel 2 Inoperable CONDITIONS PRIOR TO OCCURRENCE:
i l
Operational Mode 1, Reactor Power 100%
DESCRIPTION OF OCCURRENCE:
At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, the Control Room Operator observed a loss of indication on Channel 2 Reactor Coolant Flow.
A routinely scheduled channel functional test which does not check flow indication had been satis-factorily completed at 1027 hours0.0119 days <br />0.285 hours <br />0.0017 weeks <br />3.907735e-4 months <br />.
Performance Department was notified and Action Statement No. 7 for Technical Specification 3.3.1.1.1 was implemented.
At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />, repairs had been completed and the channel was returned to service.
The Action Statement was terminated.
All redundant channels were available during this occurrence.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
The cause of this occurrence was loss of output from the signal isolator which supplies flow indication.
The cause of the signal isolator failure is under investigation and is being followed on O.I.
752.
ANALYSIS OF OCCURRENCE:
Technical Specification 3.3.1.1.1 Action Statement No. 7 states that with the number of operational channels one less than the total number of channels, startup and/or power operation may proceed until perform-ance of the next required channel functional test provided the operational char 31 is placed in the tripped condition within one hour.
No. 12 RC Flow innel 2 was placed in the tripped condition and re-mained tripped u; il the channel was declared operational.
,LER 78-62/03L
- CORRECTIVE ACTION:
The failed signal isolator was replaced with a unit taken from spares.
The spare isolator was bench tested prior to installation into the i
protective system.
Flow indication was compared with other channels and found satisfactory.
The failed signal isolator is under investigation.
FAILURE DATA:
Signal Isolator Model 110 Manufacturer:
Westinghouse Electric Corporation Hagan/ Computer System Division Prepared by A. W.
Kapple
/
E
/
Manager - Salem Generating Statio SORC Meeting No.
58-78 l
l
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LICENSEE EVENT REPORT
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8 80 61 DOCKET NUMSER 68 69 EVENT QATE 24 75 AEPomT DAT8 80 EVENT OESCRIPTION AND PROBABLE CONSEQUENCES h lol2l lDuring normal operation, at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, the Reactor Operator noticed j
10!3; I No. 12 Reactor Coolant Flow Channel 2 was not indicating.
T/S 3.3.1.1.ll Iotall Action Statement 7 was implemented.
Performance Department placed the l
channel in the tripped condition and repaired.
All redundant channels l io;3i i s o is i l were operational.
At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />, #12 RC Flow Ch 2 was declared opera-l Io67ll tional and the Action Statement was terminated.
This is the sixth I
loisiIoccurrence of this type.
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87 CAUSE CESCRIPTION AND CORRECTIVE ACTIONS h l i j o l l The cause of this occurrence was f ailure of a Hagan Controls Signal I
titiil Isolator.
The cause of the isolator failure is under investigation.
l i,,lThe signal isolator was replaced and an operational test confirmed l
i,;3 l operability.
l 1
litai I 80 7
8 9
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% power CTWER STATUS Dis RY DISCOVERY OESCRirTION
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NRC WE ONLY ufe l
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Kapple I600)365-7000 Salen Ec.!
PHONE:
NAME OF PmEPARER 528
. _ _..